ML12011A216
| ML12011A216 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 12/27/2011 |
| From: | Operations Branch III |
| To: | FirstEnergy Nuclear Generation Corp |
| References | |
| Download: ML12011A216 (8) | |
Text
2011 Initial License Audit Exam K/A Listing K/A Q.1 000A04 AK2.2 Knowledge of the interrelations between the (Turbine Trip) and the following:
Facilitys heat removal systems, including primary coolant, emergency coolant, the decay heat removal systems, and relations between the proper operation of these systems to the operation of the facility.
K/A Q.2 000015 AA1.22 Ability to operate and / or monitor the following as they apply to the Reactor Coolant Pump Malfunctions (Loss of RC Flow): RCP seal failure/malfunction K/A Q.3 059 K4.08 Knowledge of MFW design feature(s) and/or interlock(s) which provide for the following:
Feedwater regulatory valve operation (on basis of steam flow, feed flow mismatch)
K/A Q.4 000058 AK3.02 Knowledge of the reasons for the following responses as they apply to the Loss of DC Power: Actions contained in EOP for loss of dc power K/A Q.5 000A04 AK2.1 Knowledge of the interrelations between the (Turbine Trip) and the following:
Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.
K/A Q.6 000007 EA1.08 Ability to operate and monitor the following as they apply to a reactor trip: AFW System K/A Q.7 000028 AK2.02 Knowledge of the interrelations between the Pressurizer Level Control Malfunctions and the following: Sensors and detectors K/A Q.8 000009 EK2.03 Knowledge of the interrelations between the small break LOCA and the following:
S/Gs K/A Q.9 062 K1.03 Knowledge of the physical connections and/or cause/effect relationships between the ac distribution system and the following systems: DC distribution K/A Q.10 000015 AA1.09 Ability to operate and / or monitor the following as they apply to the Reactor Coolant Pump Malfunctions (Loss of RC Flow): RCS temperature detection subsystem K/A Q.11 000028 AK3.02 Knowledge of the reasons for the following responses as they apply to the Loss of Reactor Coolant Makeup: Actions contained in SOPs and EOPs for RCPs, loss of makeup, loss of charging, and abnormal charging K/A Q.12 000055 EA2.02 Ability to determine or interpret the following as they apply to a Station Blackout:
RCS core cooling through natural circulation cooling to S/G cooling K/A Q.13 008 K4.01 Knowledge of CCWS design feature(s) and/or interlock(s) which provide for the following:
Automatic start of standby pump K/A Q.14 2.2.25 Knowledge of the bases in Technical Specifications for limiting conditions for operations and safety limits.
K/A Q.15 000054 AK2.01 Knowledge of the interrelations between the Loss of Main Feedwater (MFW) and the following: Valves K/A Q.16 000038 EA2.12 Ability to determine or interpret the following as they apply to a SGTR: Status of MSIV activating system K/A Q.17 000054 AK1.01 Knowledge of the operational implications of the following concepts as they apply to Loss of Main Feedwater (MFW): MFW line break depressurizes the S/G (similar to a steam line break)
K/A Q.18 000A03 AK2.1 Knowledge of the interrelations between the (Loss of NNI-Y) and the following:
Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.
K/A Q.19 000055 EK3.02 Knowledge of the reasons for the following responses as the apply to the Station Blackout: Actions contained in EOP for loss of offsite and onsite power K/A Q.20 062 K1.03 Knowledge of the physical connections and/or cause/effect relationships between the ac distribution system and the following systems: DC distribution K/A Q.21 000065 AK3.08 Knowledge of the reasons for the following responses as they apply to the Loss of Instrument Air: Actions contained in EOP for loss of instrument air K/A Q.22 064 K4.02 Knowledge of ED/G system design feature(s) and/or interlock(s) which provide for the following: Trips for ED/G while operating (normal or emergency)
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2011 Initial License Audit Exam K/A Listing K/A Q.23 000040 AK3.04 Knowledge of the reasons for the following responses as they apply to the Steam Line Rupture: Actions contained in EOPs for steam line rupture K/A Q.24 000001 AK1.14 Knowledge of the operational implications of the following concepts as they apply to Continuous Rod Withdrawal: Interaction of ICS control stations as well as purpose, function, and modes of operation of ICS K/A Q.25 000003 AA1.05 Ability to operate and / or monitor the following as they apply to the Dropped Control Rod: Reactor power - turbine power K/A Q.26 004 K4.07 Knowledge of CVCS design feature(s) and/or interlock(s) which provide for the following:
Water supplies K/A Q.27 015 K4.07 Knowledge of NIS design feature(s) and/or interlock(s) provide for the following:
Permissives K/A Q.28 2.2.40 Ability to apply Technical Specifications for a system.
K/A Q.29 000037 AK1.02 Knowledge of the operational implications of the following concepts as they apply to Steam Generator Tube Leak: Leak rate vs. pressure drop K/A Q.30 059 A1.07 Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the MFW controls including Feed Pump speed, including normal control speed for ICS K/A Q.31 103 A1.01 Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the containment system controls including: Containment pressure, temperature, and humidity K/A Q.32 041 K2.02 Knowledge of bus power supplies to the following: ICS inverter breakers K/A Q.33 003 K1.03 Knowledge of the physical connections and/or cause-effect relationships between the RCPS and the following systems: RCP seal system K/A Q.34 004 A4.06 Ability to manually operate and/or monitor in the control room: Letdown isolation and flow control valves K/A Q.35 005 K4.01 Knowledge of RHRS design feature(s) and/or interlock(s) which provide or the following:
Overpressure mitigation system K/A Q.36 006 K1.02 Knowledge of the physical connections and/or cause/effect relationships between the ECCS and the following systems: ESFAS K/A Q.37 022 A3.01 Ability to monitor automatic operation of the CCS, including: Initiation of safeguards mode of operation K/A Q.38 010 A1.07 Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the PZR PCS controls including: RCS pressure K/A Q.39 008 K6.04 Knowledge of the effect of a loss or malfunction on the following will have on the CCW:
Pumps K/A Q.40 010 A3.02 Ability to monitor automatic operation of the PZR PCS, including: PZR pressure K/A Q.41 011 A1.01 Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the PZR LCS controls including: PZR level and pressure K/A Q.42 2.1.7 Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation.
K/A Q.43 Plant specific priority - not in K/A catalog K/A Q.44 000E05 EK1.3 Knowledge of the operational implications of the following concepts as they apply to the (Excessive Heat Transfer) Annunciators and conditions indicating signals, and remedial actions associated with the (Excessive Heat Transfer).
K/A Q.45 012 A2.02 Ability to (a) predict the impacts of the following malfunctions or operations on the RPS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Loss of instrument power K/A Q.46 2.2.40 Ability to apply Technical Specifications for a system.
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2011 Initial License Audit Exam K/A Listing K/A Q.47 014 K5.02 Knowledge of the operational implications of the following concepts as they apply to the RPIS: RPIS independent of demand position K/A Q.48 2.2.22 Knowledge of limiting conditions for operations and safety limits.
K/A Q.49 059 A1.01 Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the MFW controls including: Location, limits, and normal ranges for level, pressure flow, temperature, and RPM measurements associated with the MFW system K/A Q.50 059 A3.03 Ability to monitor automatic operation of the MFW, including: Feedwater pump suction flow pressure K/A Q.51 002 A1.08 Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the RCS controls including: RCS average temperature K/A Q.52 061 K1.06 Knowledge of the physical connections and/or cause/effect relationships between the AFW and the following systems: Cooling water K/A Q.53 062 K4.04 Knowledge of ac distribution system design feature(s) and/or interlock(s) which provide for the following: Protective relaying K/A Q.54 000040 AA1.10 Ability to operate and / or monitor the following as they apply to the Steam Line Rupture: AFW system K/A Q.55 062 K1.03 Knowledge of the physical connections and/or cause/effect relationships between the ac distribution system and the following systems: DC distribution K/A Q.56 072 A1.01 Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the ARM system controls including: Radiation levels K/A Q.57 076 K2.08 Knowledge of bus power supplies to the following: ESF-actuated MOVs K/A Q.58 078 K4.02 Knowledge of IAS design feature(s) and/or interlock(s) which provide for the following:
Cross-over to other air systems K/A Q.59 078 K3.02 Knowledge of the effect that a loss or malfunction of the IAS will have on the following:
Systems having pneumatic valves and controls K/A Q.60 035 A2.05 Ability to (a) predict the impacts of the following malfunctions or operations on the SGs; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Unbalanced flows to the S/Gs K/A Q.61 015 K5.02 Knowledge of the operational implications of the following concepts as they apply to the NIS: Discriminator/compensation operation K/A Q.62 011 A2.10 Ability to (a) predict the impacts of the following malfunctions or operations on the PZR LCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Failure of PZR level instrument - high K/A Q.63 062 K2.01 Knowledge of bus power supplies to the following: Major system loads K/A Q.64 027 A2.01 Ability to (a) predict the impacts of the following malfunctions or operations on the CIRS; and (b) based on those predictions, use Procedures to correct, control, or mitigate the consequences of those malfunctions or operations: High temperature in the filter system (Not an exact K/A match, but same concept)
K/A Q.65 073 K1.01 Knowledge of the physical connections and/or cause/effect relationships between the PRM system and the following systems: Those systems served by PRMs K/A Q.66 2.2.44 Ability to interpret control room indications to verify the status and operation of a system, and understand how operator actions and directives affect plant and system conditions.
K/A Q.67 041 K4.17 Knowledge of SDS design feature(s) and/or interlock(s) which provide for the following:
Reactor trip K/A Q.68 2.1.7 Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation.
K/A Q.69 071 A1.03 Ability to predict and/or monitor changes in parameters(to prevent exceeding design limits) associated with Waste Gas Disposal System operating the controls including: Holdup tank pressure and level Page 3 of 5
2011 Initial License Audit Exam K/A Listing K/A Q.70 004 K3.02 Knowledge of the effect that a loss or malfunction of the CVCS will have on the following:
PZR LCS K/A Q.71 2.4.12 Knowledge of general operating crew responsibilities during emergency operations.
K/A Q.72 2.4.21 Knowledge of the parameters and logic used to assess the status of safety functions, such as reactivity control, core cooling and heat removal, reactor coolant system integrity, containment conditions, radioactivity release control, etc.
K/A Q.73 2.2.13 Knowledge of tagging and clearance procedures.
K/A Q.74 2.4.18 Knowledge of the specific bases for EOPs.
K/A Q.75 012 K1.02 Knowledge of the physical connections and/or cause/effect relationships between the RPS and the following systems: 125V dc system Page 4 of 5
2011 Initial License Audit Exam K/A Listing SRO ONLY K/A Q.76 2.2.12 Knowledge of surveillance procedures.
K/A Q.77 2.4.16 Knowledge of EOP implementation hierarchy and coordination with other support procedures or guidelines such as, operating procedures, abnormal operating procedures, and severe accident management guidelines.
K/A Q.78 2.2.14 Knowledge of the process for controlling equipment configuration or status.
K/A Q.79 000009 EA2.23 Ability to determine or interpret the following as they apply to a small break LOCA:
RCP operating parameters and limits K/A Q.80 2.2.40 Ability to apply Technical Specifications for a system.
K/A Q.81 000065 AA2.08 Ability to determine and interpret the following as they apply to the Loss of Instrument Air: Failure modes of air-operated equipment K/A Q.82 000011 EA2.03 Ability to determine or interpret the following as they apply to a Large Break LOCA:
Consequences of managing LOCA with loss of CCW K/A Q.83 000062 AA2.03 Ability to determine and interpret the following as they apply to the Loss of Nuclear Service Water: The valve lineups necessary to restart the SWS while bypassing the portion of the system causing the abnormal condition K/A Q.84 000E03 EA2.2 Ability to determine and interpret the following as they apply to the (Inadequate Subcooling Margin) Adherence to appropriate procedures and operation within the limitations in the facility*s license and amendments.
K/A Q.85 000036 AA2.02 Ability to determine and interpret the following as they apply to the Fuel Handling Incidents: Occurrence of a fuel handling incident K/A Q.86 000E04 EA2.1 Ability to determine and interpret the following as they apply to the (Inadequate Heat Transfer) Facility conditions and selection of appropriate procedures during abnormal and emergency operations.
K/A Q.87 2.1.5 Ability to use procedures related to shift staffing, such as minimum crew complement, overtime limitations, etc.
K/A Q.88 000036 AA1.01 Ability to operate and / or monitor the following as they apply to the Fuel Handling Incidents: Reactor building containment purge ventilation system K/A Q.89 2.4.25 Knowledge of fire protection procedures.
K/A Q.90 2.4.4 Ability to recognize abnormal indications for system operating parameters that are entry-level conditions for emergency and abnormal operating procedures.
K/A Q.91 2.4.29 Knowledge of the emergency plan.
K/A Q.92 056 A2.04 Ability to (a) predict the impacts of the following malfunctions or operations on the Condensate System; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Loss of condensate pumps K/A Q.93 000065 AK3.08 Knowledge of the reasons for the following responses as they apply to the Loss of Instrument Air: Actions contained in EOP for loss of instrument air K/A Q.94 2.1.42 Knowledge of new and spent fuel movement procedures.
K/A Q.95 2.1.40 Knowledge of refueling administrative requirements.
K/A Q.96 2.2.40 Ability to apply Technical Specifications for a system.
K/A Q.97 2.3.4 Knowledge of radiation exposure limits under normal or emergency conditions.
K/A Q.98 2.1.45 Ability to identify and interpret diverse indications to validate the response of another indication.
K/A Q.99 2.4.40 Knowledge of SRO responsibilities in emergency plan implementation.
K/A Q.100 000E13 EA2.1 Ability to determine and interpret the following as they apply to the (EOP Rules)
Facility conditions and selection of appropriate procedures during abnormal and emergency Page 5 of 5
JPM JPM TITLE Type Used IN JPM JPM TITLE Type Used JPM- SRO - Review a Waste Gas Release with NO Radiation ADM Audit JPM- RO,SRO - Check Out a Radiation Detector in the RRA ADM NRC 175 Monitors Available 149 Exa JPM- RO,SRO - Manual Heat Balance ADM Audit JPM- RO,SRO - Perform A Boric Acid Batch Calculation (DB-OP-06001 ADM NRC 216 228 Attach 2) Exa JPM- RO - ADJUST RE1878A WARNING AND HIGH ADM Audit JPM- RO,SRO - Control of Locked Valves During Post Maintenance ADM NRC 260 SETPOINTS 261 Testing Exa JPM- SRO - Determine the Appropriate Protective Action ADM Audit JPM- RO Calculate Boron Conc for SDM of 1%k/k with 2 stuck rods ADM NRC 150 Recommendations New Exa JPM- RO,SRO - Identify CTMT Spray Pump 1 is Outside ADM Audit JPM- RO Generate a tagout for CNMT spray ADM NRC 152 Acceptable Range on Avg. Pump Differential Pressure New Exa JPM- RO,SRO - Calculate Estimated Critical Boron ADM Audit JPM- SRO Determine Compensatory actions for failed Deluge valve on ADM NRC 059 Concentration New EDG fire protection Exa JPM- RO,SRO - Control Room Evacuation, Reactor Operator SIM Audit JPM- SRO Classify an event & complete the initial notification form ADM NRC 004 Actions in the Control Room New Exa JPM- RO,SRO - Shutdown a MFPT During a Rapid Plant SIM Audit JPM- RO,SRO - Establishing Long Term Boron Dilution with LPI Train 2 SIM NRC 012 Shutdown 002 Exa JPM- RO,SRO - Place E2 and F2 on Alternate and Remove SIM Audit JPM- RO,SRO - Vacuum and Gland Steam Systems Actions During a SIM NRC 111 Transformers AE2 and AF2 from Service 113 Loss of Instrument Air Exa JPM- RO,SRO - Shutdown Control Room Emergency SIM Audit JPM- RO,SRO - Energize an RPS Channel 2 SIM NRC 124 Ventilation System 121 Exa JPM- RO,SRO - Operate the Hydrogen Purge/Dilution Systems SIM Audit JPM- RO,SRO Isolate SG with SGTR SIM NRC 141 197 Exa JPM- RO,SRO - Perform a Blast Cooldown of the RCS SIM Audit JPM- RO,SRO Perform Control rod exercise with malfunction SIM NRC 158 New Exa JPM- RO,SRO - Establish Long Term Boron Dilution with Prz SIM Audit JPM- RO,SRO Perform CNMT pressure reduction release with SIM NRC 160 Aux Spray New malfunctions Exa JPM- RO Transfer Non-Essential CCW Isolation Valves from SIM Audit JPM- RO,SRO Perform PRZR boron equalization w/PRZR spray SIM NRC 184 Line 1 to Line 2 New malfunction Exa JPM- RO,SRO - Perform Attachment 4 of DB-OP-02531, OTSG PL Audit JPM- RO,SRO Perform 13.8KV live bus transfer w/malfunctions SIM NRC 040 Tube Leak 220 Exa JPM- RO, SRO Fill CCW System PL Audit JPM- RO,SRO - Swap to a Swing Battery Charger PL NRC 195 069 Exa JPM- RO,SRO - Transfer an Essential Instrument AC Panel PL Audit JPM- RO,SRO - Resetting the AFPT Overspeed Trip Mechanism After PL NRC 050 from Normal to Alternate Power Supplies 075 and Auto Start Exa JPM- RO,SRO - Establish High Pressure Injection Alternate Minimum PL NRC 256 Recirc Flowpath Exa
JPM- RO,SRO - Loss of Service Water Loop 1 to Primary SIM Last 2 JPM- SRO - Perform An On-Line Risk Determination For A Change In ADM Last 014 Loads NRC 240 A System Lineup NRC JPM- RO,SRO - RPS Shutdown Bypass Trip Switch Operation SIM Last 2 JPM- RO,SRO - Calculate RCS Flow With Computer Point F744 ADM Last 021 NRC 227 Unavailable NRC JPM- RO,SRO - Transfer LPI Suction to the Emergency Sump SIM Last 2 JPM- SRO - Security Event Classification and Notification ADM Last 033 NRC 178 NRC JPM- RO,SRO - Purge Containment in Mode 5 SIM Last 2 JPM- RO, SRO Calculate Steam Generator Leakrate ADM Last 085 NRC New NRC JPM- RO,SRO - Manually Initiate SFAS SIM Last 2 JPM- RO, SRO Review a safety tagout for High Pressure Injection ADM Last 097 NRC New Pump 1 with eSOMS unavailable NRC JPM- RO,SRO - Fill a Core Flood Tank SIM Last 2 JPM- SRO Review Auxiliary Feedwater Pump 2 Monthly Periodic Test ADM Last 132 NRC New and Determine Operability NRC JPM- RO,SRO - Station Vent High Radiation Response SIM Last 2 JPM- RO, SRO Determine components for Tagout of CCW Pump #1 ADM Last 215 NRC New NRC JPM- RO,SRO - CRD Sequence Fault Recovery SIM Last 2 JPM- RO, SRO Don Anti-C clothing ADM Last 221 NRC New NRC JPM- RO,SRO - Perform the Main Turbine Overspeed Trip Test SIM Last 2 JPM- RO, SRO Review Miscellaneous Shift Checks ADM Last 237 NRC New NRC JPM- RO, SRO Reset Tripped RPS SIM Last 2 JPM- RO, SRO Offsite Notifications following Turbine Damage ADM Last New NRC New NRC JPM- RO, SRO Energize Bus D1 from Bus B SIM Last 2 JPM- SRO Review Offsite AC Source Line-up Surveillance ADM Last New NRC New NRC JPM- RO, SRO Spray Containment Post LOCA SIM Last 2 JPM- (NLO, RO, SRO) Notify State and Counties on an Alert ADM Last New NRC 241 NRC JPM- RO, SRO Initiate MU/HPI Cooling SIM Last 2 JPM- NLO,RO,SRO - Emergency Shutdown of an Emergency Diesel PL Last New NRC 115 Generator NRC JPM- RO, SRO Respond to Low RCS pressure Condition SIM Last 2 JPM- NLO,RO,SRO - Emergency Startup of Startup Feedwater Pump PL Last New NRC 118 NRC JPM- RO, SRO Exercise Group 5 Rods SIM Last 2 JPM- NLO,RO,SRO - Actions for Steam Binding of MDFP PL Last New NRC 127 NRC JPM- SIM Last 2 JPM- RO,SRO - Recovery from High Radiation in the Fuel Handling PL Last New RO, SRO Synchronize the Main Generator to the Grid NRC 037 AREA NRC 2011 NRC Exam JPMs JPM- RO, SRO Restore the Makeup System During a Control Room PL Last New Evacuation NRC JPMs Used on the Last 2 NRC exams JPM- PL Last New RO, SRO Recirc BWST NRC 2011 Audit Exam JPMs
Au NRC CRITICALS MALFUNCTIONS CRITICALS MALFUNCTIONS dit Close AF 608, AFW to SG 1 1 Close RC-11, PORV Block 2% Raise power to 4% 5% 1 and Continue Rx startup to about 14%.
Close Spray Valve RCS Pressure ch sel for NNI fails HI open Atmos Vent Valve 1 Place MFP in service Feed one SG at < 1000 gpm BA Pump 2 trips Sheared shaft on Condensate Pump 1 Main Turbine Turning Gear Locks Out Establish MU/HPI Cooling Slow fail of LT SP9B4, to 0; SG 1 S/U Lvl xmitter Circ Wtr Sys rupture in the Pump house steam leak on AFPT 2; MS 107A failed open Two stuck rods AFPT 1 Gov. @ 500 rpm results in loss of FW Both AFPTs trip on overspeed Motor driven feed pump bkr will not close.
2 Trip All RCPs line up and start HPI piggyback 70% Controlled power reduction 100% 2 SFAS CNMT Press xmitter fails manually start LPI Pump 1 min SCM during RCS C/D. Hi vib on MFPT #1 - manual trip HP FW Heater Tube leak ICS AUTO Runback fails Controlled power reduction RCS Press sel for NNI input fails LO SAC #2 trips and SAC #1 fails to load 120VAC Inverter alarm Emer IAC fails to AUTO start.
OTSG Tube Leak Bus D1 locks out MFPT #2 trips Rapidly progressing RCS leak rate OTSG tube leak to rupture after RX trip SFAS L3 Output Module Failure Isol AFW flow to the OTSG PZR Spray Valve fails CLOSED 100% RCS press xmitter PT6365B fails (TS ) 3 3 Xfer Gland Steam from MS to Aux Re-power D2 Bus 60% B/D SG 1 Steam power @ direction of Sys Dispatcher Start the MDFP AFW Pump 1 has no Governor oil (TS) Deaerator level transmitter fails low PRZR LCV (MU 32) fails to operate in auto PZR PORV leakage (TS)
Control Rod drop (TS) AC Xformer lockout (TS)
Loss of NNI X DC Makeup Tank level transmitter fails Loss of Offsite AC Main Steam leak (large) inside CNMT EDG 1 fails to auto start Both trainsSFAS act fails; AF 3870 fails to close Trip Rx B/4 cond vac 10 Swap Letdown Purification Demineralizers for Li+
AFW Pump 2 governor valve closes HgA 95% 4 Control 4 Deenergize E2 and F2 80% Containment Spray Pump 1 oil leak Init AFW & Isol MFW & MS BWST Lo-Lo Level Inst (LI 1525A) Fails (TS)
SAC #2 trips, SBY AC Fails to Auto Start Trip all RCPs RCP 1-1 Seal Fail, pwr to stop RCP 1-1 Circ Water Pump #4 Trips / Power Reduction Manually start an HPI Pump Selected T-H xmitter (TT RC3A1) fails RCP 1-2 Breaker trip Vacuum Leak HP Condenser / Reactor Trip SFRCS Man PBs in C/R Fails/ManAct at SFRCS ATWS cabinets Reactor Trip Failure from high condenser Pressurizer Safety fails open pressure.